ASCE will be sunsetting the Civil Engineering Database (CEDB) in the coming months. We encourage you to start using the ASCE Library to perform content searches. In the ASCE Library, you can save your search results as well as receive email content alerts when new content relevant to your area of interest is published. Try it out today at https://ascelibrary.org.

 

An Assessment of Coupled Thermal-Hydrologic-Mechanical-Chemical Processes
A literature review was conducted to determine the state of knowledge available in the modeling of coupled thermal (T), hydrologic (H), mechanical (M), and chemical (C) processes relevant...

Geochemistry for High Level Waste: An International Comparison
This paper presents a brief summary of some of the recent and on going geochemical research related to the disposal of high level radioactive waste. For most categories of research (basic...

Experience in Modeling for Environmental Physics and Biogeochemistry
This report is a short review of the author's personal experience on phys.-math. and system-logical modeling of migration and transport processes (MTP) of radionuclides, trace-elements...

Post-Irradiation Fuel Assembly Dimensions for Transportation and Storage Cask Designs
When designing casks for the shipment of Spent Nuclear Fuel (SNF), one of the most important considerations is the external dimensions of the fuel assemblies to be shipped. Since SNF assemblies...

Code Requirement for Concrete Repository and Processing Facilities
Because of varied uses and performance/safety requirements of concrete for high, medium and low level radioactive wastes, a review of the current ACI 349 Code document was carried out...

Radionuclide Transport in Fractured Media
Until recently, the classical advective-dispersive transport equation was considered to be an adequate model for describing the motion of a solute (e.g. radionuclides) in porous and fractured...

Quality-Assurance Program Description Defense Waste Processing Facility
This paper describes the Westinghouse Savannah River Company's (WSRC) quality assurance program for defense-waste processing at the Savannah River Site (SRS). WSRC is the operating contractor...

Disposal of Defense Spent Fuel and HLW from the Idaho Chemical Processing Plant
Acidic high-level radioactive waste (HLW) resulting from fuel reprocessing at the Idaho Chemical Processing Plant (ICPP) for the U. S. Department of Energy (DOE) has been solidified to...

Plutonium and Minor Actinide Transmutation by Long Irradiation in LWR
An investigation was made on the conceptual possibility of burning in a thermal reactor MOX fuel together with special pins containing plutonium, minor actinides and long-lived fission...

ATW System Impact on High-Level Waste
Criteria are developed for transmutation system impact on HLW storage that are related to intrusion and long-term risk reduction. Thermal reactor, fast reactor, and accelerator-driven,...

Remote Spent Fuel Handling in France at the La Hague Cask Unloading Facility
French policy for the back end of fuel cycle is based on spent fuel reprocessing. Irradiated spent fuels are transferred in casks from the nuclear reactors to the reprocessing plant where...

Simulated Hanford Waste: A Study of Physical Properties, Gas Retention, and Gas Generation
This study helps to establish the physical and chemical processes responsible for the generation and retention of gases within high-level waste contained in Tank 101-SY on the Hanford...

Evaluation of Spent Fuel Behavior Under Interim Storage Conditions in Russia
The nuclear power in Russia is based on three types of water cooled power reactors VVER-440, -1000 and RBMK-1000. Two fast sodium cooled reactors-prototypes BN-350 and BN-600 are in commercial...

Evaluation of Neutron Emission from Vitrified HLW Compositions
Neutron radiological hazards from vitrified HLW are important for handling and transportation - especially if the concept of separate storage of concentrated transuranics is adopted, as...

Use of Coupled Geochemical and Transport Calculations for Nuclear Waste Problems
The dissolution and migration of radionuclides from a final repository for radioactive waste is complex chemically. The dissolution and release rates depend on the chemistry and on advective...

Surface Complexation Model Prediction of Np and Pu Distribution Coefficients
Robust estimates of radionuclide sorption coefficients (K_d) are needed to estimate radionuclide retardation during ground-water transport from a...

??⁴U/??⁸U as a Ground-Water Tracer, SW Nevada-SE California
The ²³⁴U/²³⁸U ratio of uranium in oxidizing ground waters is potentially an excellent ground-water tracer...

Evaluation of Borosilicate Glass as a High-Level Radioactive Waste Form
The choice of a borosilicate glass as a high-level nuclear waste form is evaluated base on observations of natural and artifical glass hydration and reaction, experimental results of glass...

The Effect of Gamma Irradiation on the Volatility and Redox State of Simulated DWPF High-Level Nuclear Waste Glasses
Gamma-induced volatility of simulated DWPF high-level nuclear waste glasses is highly dependent upon the redox state of the glass. For oxidized glasses with an Fe²⁺/(Fe²⁺...

Hanford Ferrocyanide Reactivity: Effects of Other Tank Constituents
In this study simulated wastes were used to determine the effect of potential waste constituents on the reactivity and explosivity of Hanford ferrocyanide-bearing wastes. Test results...

 

 

 

 

Return to search